In this study, the steady-state and transient critical heat fluxes (CHFs) in pool boiling were measured on 1.0 mm diameter horizontal cylinders of gold and platinum heaters under saturated conditions due to transient heat inputs, Q0exp(t/τ), in a pool of Fluorinert FC-72. Heaters were heated by electric current with the periods, τ, ranged from 10 ms to 20 s, and the pressures ranged from atmospheric up to around 1.2 MPa. The steady-state CHFs measured are dependent on pressure and almost agree with the values obtained by Kutateladze’s correlation based on hydrodynamic instability (HI) model. It was considered that the boiling inception and the direct transition during the steady-state period occur by the pre-pressure of ∼1.2 MPa. The trend of typical transient CHFs were clearly divided into the first, second, and third groups for long, short, and intermediate periods, respectively. The direct transition processes to film boiling without nucleate boiling for the short periods obtained from both heaters were confirmed due to the heterogeneous spontaneous nucleation (HSN) in flooded cavities on the cylinder surface. The empirical correlations to express each of corresponding CHFs measured on both heaters for the short periods are presented in this paper.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4245-2
PROCEEDINGS PAPER
Transient Pool Boiling Critical Heat Flux of FC-72 Under Saturated Conditions
Sutopo P. Fitri,
Sutopo P. Fitri
Kobe University, Graduate School of Science and Technology, Kobe, Hyogo, Japan
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Katsuya Fukuda,
Katsuya Fukuda
Kobe University, Graduate School of Science and Technology, Kobe, Hyogo, Japan
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Qiusheng Liu,
Qiusheng Liu
Kobe University, Graduate School of Science and Technology, Kobe, Hyogo, Japan
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Jongdoc Park
Jongdoc Park
Oshima National College of Maritime Technology, Suo-Oshima-cho, Yamaguchi, Japan
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Sutopo P. Fitri
Kobe University, Graduate School of Science and Technology, Kobe, Hyogo, Japan
Katsuya Fukuda
Kobe University, Graduate School of Science and Technology, Kobe, Hyogo, Japan
Qiusheng Liu
Kobe University, Graduate School of Science and Technology, Kobe, Hyogo, Japan
Jongdoc Park
Oshima National College of Maritime Technology, Suo-Oshima-cho, Yamaguchi, Japan
Paper No:
ICONE14-89394, pp. 617-625; 9 pages
Published Online:
September 17, 2008
Citation
Fitri, SP, Fukuda, K, Liu, Q, & Park, J. "Transient Pool Boiling Critical Heat Flux of FC-72 Under Saturated Conditions." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Miami, Florida, USA. July 17–20, 2006. pp. 617-625. ASME. https://doi.org/10.1115/ICONE14-89394
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